ML20066B077
| ML20066B077 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 10/21/1982 |
| From: | Adensam E Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20066B080 | List: |
| References | |
| NUDOCS 8211060376 | |
| Download: ML20066B077 (5) | |
Text
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l TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-327 SEQUOYAH NUCLEAR PLANT, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE f
Amendment No. 16 License No. DPR-77 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment to the Sequoyah Nuclear Plant. Unit 1 (the facility) Facility Operating License No. DPR-77 filed by the Tennessee Valley Authority (licensee), dated July 15, 1982, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's regulations as set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the license, as amended, the provisions of the Act, and the rules and regulations of the Com-mission; C.
There is reasonable assurance (1) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is hereby amended by page changes to the Appendix A Technical Specifications as indicated in the attcchments to this license amend-ment and paragraph 2.C.(2) of Facility Operating License No. DPR-77 is hereby amended to read as follows:
l-(2) Technical Specifications The Technical Specifications contained in Appendi:t A, as revised through Amendment No.16, are hereby incorporated into the license.
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. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
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Y 1,
Elinor G. Adensam. Chief Licensing Branch No. 4 Division of Licensing Attactrnent:
Appendix A Technical Specification Changes Date of Issuance: October 21, 1982 V.
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ATTACHMENT TO LICENSE AMENDMENT NO. 16 FACILITY OPERATING LICENSE NO. DPR-77 DOCKET NO. 50-327 i
Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages, lhe revised pages are identified by Amendment number and contain vertical lines indicating the area of change.
Amended Page 2-6 3/4 3-27 omcc>
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. * * * * *... * = * *... *. * *.
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i TABLE 2.2-1 (Continued)
REACTOR TRIP SYSTEM INSTRUMENTATION TRIP SETPOINTS S
E FUNCTIONAL UNIT TRIP SFTP0 INT ALLOWABLE VALUES C5
- 13. Steam Generator Water
> 18% of narrow range instrument
> 17% of narrow range instrument Level--Low-Low ipan-each steam generator ipan-each steam generator w
- 14. Steam /Feedwater Flow
. < 40% of full steam flow at
< 42.5% of full steam flow at-t Mismatch and Low Steam RATED THERMAL POWER coincident RATED THERMAL POWER coincident Generator Water Level with steam generator water level
.with steam generator water level 1 25% of narrow range instru-1 24.0% of narrow range instru-ment span-each steam generator ment span-each t, team generator
- 15. Undervoltage-Reactor 1 4830 volts-each bus 1 4761 volts-each bus Coolant Pumps
- 16. Underfrequency-Reactor 1 56.0 Hz each bus 2 55.9 Hz each bus
'?
Coolant Pumps e
- 17. Tu'rbine Trip A.
Low Trip System 1 45 psig 1 43 psig Pressure B.
Turbine Stop Valve 1 1% open 1 1% open Closure
- 18. Safety Injection Input Not Applicable Not Applicable from ESF
-10
-II
- 19. Intermediate Range Neutron 1 1 x 10 amps 16 x 10 amps Flux - (P-6) Enable Block Source Range Reactor Trip 5a
- 20. Power Range Neutron Flux
< 10% of RATED
< 11% of RATED g
(not P-10) Input.to Low Power THERMAL POWER THERMAL POWER E
Reactor Trips Block P-7 5
t 5
TABLE 3.3-4 (Continued)
.m ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION TRIP SETPOINTS S!
7 FUNCTIONAL UNIT TRIP SETPOINT ALLOWABLE VALUES
.E 6.
Manual Not Applicable Not Applicable w
b.
Automatic Actuation Logic Not Applicable Not Applicable c.
Main Steam Generator Water Level-low-low
> 18% of narrow range
> 17% of narrow range Instrument span each Instrument span each steam generator steam generator d.
S.I.
See 1 above (all SI Setpoints) h e.
Station Blackout 0 volts with a 5.0 second 0 volts with a 5.0 1 1.0 second time delay time delay b
f.
Trip of Main Feedwater N.A.
N.A.
+
Pumps w
O g'.
Auxiliary Feedwater Suction 1 2 psig (motor driven pump) 1 1 psig (motor driven pump)
Pressure-Low 1 6.5 psig (turbine driven 2 5.5 psig (turbine driven pump) pump) 7.
LOSS OF POWER a.
6.9 kv Shutdown Board Undervoltage f.
1.
Loss of' Voltage 0 volts with a 0 volts with a 1.5 second time 1.5 0.5 second time j
delay delay 2.
Load Shedding 0 volts with a 0 volts with a 8
5.0 second time delay 5.0 i 1.0 second
[
time delay o-
~
8.
ENGINLERED SAFETY FEATURE 5
ACTUATION SYSTEM INTERLOCKS i
a.
Pressurizer Pressure Manual Block of Safety Injection P-ll < 1970 psig
< 1980 psig
,